Japan Atomic Power Company

www.japc.co.jp
Tokyo, Japan

The Japan Atomic Power Company is a company initially formed to jump start the commercial use of nuclear power in Japan, and currently operates two different sites. According to the official web site, JAPC is "the only power company in Japan solely engaged in nuclear energy".JAPC owns both units at the Tōkai Nuclear Power Plant and the Tsuruga Nuclear Power Plant with plans to expand at Tsuruga.The company is jointly owned by Japan's major electric utilities: The Tokyo Electric Power Company , Kansai Electric Power , Chubu Electric Power , Hokuriku Electric Power Company , Tohoku Electric Power , and Electric Power Development Company . Wikipedia.


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Patent
Japan Atomic Power Company, Asahi Kasei Corporation and Thermographers Co. | Date: 2016-11-16

To provide a practical infrared transmissive protective cover capable of detecting a heating abnormality of an internal heating element and the like by visual observation and by using infrared rays. The infrared transmissive protective cover includes a light transmission section, the light transmission section is made of a resin sheet containing a resin composition, and a total light transmittance of the light transmission section in a visible light region is 70% or more, and an average infrared transmittance in a wavelength range of 8 to 14 m is 5% or more.


Aoto K.,Japan Atomic Energy Agency | Uto N.,Japan Atomic Energy Agency | Sakamoto Y.,Japan Atomic Energy Agency | Ito T.,Mitsubishi Group | And 2 more authors.
Journal of Nuclear Science and Technology | Year: 2011

This paper describes the progress of the design study and research and development (R&D) for the Japan Sodium-cooled Fast Reactor (JSFR) implemented in the "Fast Reactor Cycle Technology Development (FaCT)" project. A sodium-cooled fast reactor with an electric power of 1,500MWe is targeted for commercialization at around 2050, and a demonstration reactor assuming a power output from 500 to 750MWe is planned to start operation at around 2025. R&D on innovative technologies to achieve economic competitiveness and enhance reliability and safety is carried out for the commercialization. A compact reactor vessel without a vessel wall cooling system is pursued in consideration of the wall thickness enough to resist the severest seismic condition. A two-loop cooling system with shortened highchromium steel piping is a crucial feature, and studies on the hydraulics in the pipe elbow and the fabrication capability of the pipes are being carried out. A double-walled straight tube steam generator is investigated to enhance the reliability against sodium/water reaction, and developmental works are progressing, including the thermal-hydraulic design and trial manufacturing for components. Self-Actuated Shutdown System (SASS) is being developed with safety analysis of the applicability for JSFR and experimental demonstration in the experimental fast reactor JOYO. An advanced fuel handling system is pursued to enhance economic performance. In parallel with considering the necessity of studies on alternative technologies, discussion on whether the innovative technologies can be adopted for JSFR is in progress to be finalized in 2010. © Atomic Energy Society of Japan.


Katoh A.,Japan Atomic Energy Agency | Chikazawa Y.,Japan Atomic Energy Agency | Obata H.,Japan Atomic Power Company | Kotake S.,Japan Atomic Power Company
Journal of Nuclear Science and Technology | Year: 2010

The Japan Sodium-cooled Fast Reactor (JSFR) has adopted an in-vessel fuel handling system that consists of a single rotating plug, an upper inner structure (UIS) with a vertically penetrating slit, and a fuel handling machine (FHM) with a pantograph arm enhancing a compact reactor vessel design. Since the reactor vessel design depends on the in-vessel fuel handling system, the feasibility of the JSFR compact reactor vessel design is directly related to the feasibility of the new FHM. In this study, we have fabricated a full-scale mock-up of the JSFR FHM and performed tests in air. From the tests, the FHM mock-up shows sufficient performance in terms of positioning accuracy, motion speed, and stiffness to ensure durability for practical use in commercial plants. Structural analyses have been conducted to validate and improve the seismic analysis model and the positioning control of the FHM. The numerical results are in good agreement with the vibration and positioning tests, showing that there is a sufficient possibility that the model has enough performance to conduct seismic analysis and improve positioning accuracy. © Atomic Energy Society of Japan.


Sugino W.,Japan Atomic Power Company
Nihon Kikai Gakkai Ronbunshu, B Hen/Transactions of the Japan Society of Mechanical Engineers, Part B | Year: 2013

Flow Accelerated Corrosion (FAC) of carbon steel (CS) piping is one of main issues in secondary system of Pressurized Water Reactor (PWR) nuclear power plant. Therefore, Oxygenated Water Chemistry (OWC) as a new approach to FAC suppression for PWR secondary system was applied to condensate system of Tsuruga-2 (1160 MWe PWR, commercial operation started in 1987) in Jan. 2011. To evaluate the FAC mitigation effect of OWC, wall thickness of actual condensate piping in Tsuruga-2 after OWC application was measured by continuous monitoring system, using high-temperature and high-resolution ultrasonic probe. As a result, it was demonstrated that FAC was mitigated by more than 5ppb of oxygen under Low-AVT (pH9.3) condition, and FAC was almost stopped even in 2ppb of oxygen under High-AVT (pH9.8) condition. © 2013 The Japan Society of Mechanical Engineers.


Wu J.,Waseda University | Maekawa N.,Waseda University | Maekawa N.,Japan Atomic Power Company | Oka Y.,Waseda University
Journal of Nuclear Science and Technology | Year: 2013

A supercritical-pressure light water cooled and moderated reactor (Super LWR) with a single-pass flow scheme is developed for simplifying upper core structures. Both coolant in the fuel channels and the water rods flow upward and are mixed in the upper plenum. It eliminates the moderator guide/distribution tubes in the upper core that were used in the previous Super LWR design adopting two-pass coolant flow scheme. This core design adopts a four-batch fuel management scheme and an out-in fuel loading pattern. One hundred and twenty-one fuel assemblies with an active height of 3.7 m are included. The flow rate fraction for water rods is 3.5%, and the thermal insulator is used to keep the moderator temperature below pseudocritical temperature. The equilibrium core is analyzed by using neutronic and thermal-hydraulic coupled calculation. The results show that the maximum cladding surface temperature (MCST) is limited to 485 °C with the average outlet temperature of 400°C. The inherent safety is fulfilled by the positive water density reactivity coefficient and sufficient shutdown margin. On the other hand, the investigation of average outlet coolant temperature varying with MCST is carried out to explore the maximum outlet temperature by employing current MCST criterion and single-pass core design. The average outlet temperature increases with the MCST, and it achieves 465 °C with the thermal efficiency of 43.1% at the MCST criterion of 650 °C. The structure inside the reactor pressure vessel is simplified as a pressurized water reactor. © 2013 Atomic Energy Society of Japan. All rights reserved.


Patent
Japan Atomic Power Company and Japan Atomic Energy Agency | Date: 2011-12-19

An apparatus with which areas near surfaces in a water environment that are contaminated by radioisotopes are decontaminated by non-thermal laser peeling without suffering re-melting, re-diffusing and re-contaminating. The apparatus includes a piping structure with which a substance to be irradiated that has been deposited on outer and inner surfaces of a nuclear reactor pressure vessel, and a nuclear reactor container tank, and the internal nuclear reactor structures all having been contaminated with radioisotopes, can be removed in the water environment. The piping structure, to secure a region in a water environment that is gas pressurized to discharge the water and filled with the gas to not interfere with laser irradiation, has a semi-hermetically closed, incomplete water seal that is half-open with a siphon provided downward, a mechanical structure that withstands water pressure in a radial direction, and an extendable bellows-like tube to enable the piping structure to tilt.


Patent
Japan Atomic Power Company | Date: 2013-03-25

Provided are radiation source reducing system and method for nuclear power plants whereby radiation source can be reduced. This radiation source reducing system for nuclear power plants is characterized in being provided with a dispersant injecting unit, which injects a dispersant into a coolant of a nuclear power plant coolant system.


Patent
Japan Atomic Power Company, Thermographers Co. and Asahi Kasei Corporation | Date: 2011-12-13

To provide a practical infrared transmissive protective cover capable of detecting a heating abnormality of an internal heating element and the like by visual observation and by using infrared rays. The infrared transmissive protective cover includes a light transmission section, the light transmission section is made of a resin sheet containing a resin composition, and a total light transmittance of the light transmission section in a visible light region is 70% or more, and an average infrared transmittance in a wavelength range of 8 to 14 m is 5% or more.


Patent
Japan Atomic Power Company | Date: 2015-02-04

Provided are radiation source reducing system and method for nuclear power plants whereby radiation source can be reduced. This radiation source reducing system for nuclear power plants is characterized in being provided with a dispersant injecting unit, which injects a dispersant into a coolant of a nuclear power plant coolant system.


Patent
Japan Atomic Power Company, Asahi Kasei Corporation and Thermographers Co. | Date: 2013-10-23

To provide a practical infrared transmissive protective cover capable of detecting a heating abnormality of an internal heating element and the like by visual observation and by using infrared rays. The infrared transmissive protective cover includes a light transmission section, the light transmission section is made of a resin sheet containing a resin composition, and a total light transmittance of the light transmission section in a visible light region is 70% or more, and an average infrared transmittance in a wavelength range of 8 to 14 m is 5% or more.

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